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    • 11. 发明专利
    • Addition amount calculation method by concentrated erbia credit
    • 加浓ERBIA信用额度计算方法
    • JP2010261865A
    • 2010-11-18
    • JP2009113906
    • 2009-05-08
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • YAMAZAKI MASATOSHI
    • G21C7/04G21C3/328G21C3/62
    • Y02E30/38Y02E30/39
    • PROBLEM TO BE SOLVED: To easily and accurately calculate an addition amount required for obtaining the degree of reaction equivalent to fuel of U235 concentration degree of 5% with the usage of concentrated erbia, with respect to fuel with the U235 concentration degree exceeding 5%. SOLUTION: A method for calculating the addition amount by an erbia credit with the usage of the concentrated erbia has an abundance ratio of Er167 which is equal to or more than that of natural erbia, with respect to a nuclear fuel having a given U235 concentration degree, and the addition amount ε by the erbia credit is calculated according to formula 3, wherein ε is the addition amount of the concentrated erbia, α i is the reactivity coefficient for the erbia isotopes (i represents Er164, Er165, Er166, Er167, Er168 or Er170), ν i is an isotopic composition of the concentrated erbia (i represents Er164, Er165, Er166, Er167, Er168 or Er170), β j is a reactivity coefficient of uranium isotope (j is U234, U235, U236 and U238), and μ j is an isotopic composition of uranium (j represents U234, U235, U236 or U238). COPYRIGHT: (C)2011,JPO&INPIT
    • 要解决的问题:为了容易且准确地计算使用浓缩的畏惧度获得相当于U235浓度为5%的燃料的反应程度所需的添加量,对于U235浓度超过的燃料 5%。 解决方案:使用浓缩的鄂尔比亚计算埃尔比亚信用额度的方法,相对于具有给定的核燃料的Er167的丰度比等于或大于天然呃的丰度比 U235浓度和通过铒信用的添加量ε根据公式3计算,其中ε是浓缩铒的添加量,α i是呃同位素的反应系数(i 代表Er164,Er165,Er166,Er167,Er168或Er170),ν i 是浓缩铒的同位素组成(i表示Er164,Er165,Er166,Er167,Er168或Er170),β j 是铀同位素的反应系数(j是U234,U235,U236和U238),μS是铀的同位素组成(j代表U234,U235,U236或 U238)。 版权所有(C)2011,JPO&INPIT
    • 12. 发明专利
    • Flange coupling and structure with pipe
    • 法兰联轴器和结构与管
    • JP2010133461A
    • 2010-06-17
    • JP2008308335
    • 2008-12-03
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • KITAGAWA YUJI
    • F16L23/02
    • PROBLEM TO BE SOLVED: To provide a flange coupling which is excellent in a liquid draining effect, significantly reduces the number of required wastes for wiping a liquid when being lifted up from the inside of the liquid, remarkably reduces the risk of splashing the liquid on an operator, and does not deteriorate strength, and also to provide a structure with a pipe. SOLUTION: The flange coupling is used for a piping portion of the structure with a pipe, which is used in the liquid and lifted up from the inside of the liquid as necessary, and lifted up from the inside of the liquid in almost a level state. The upper surface, which is a non-connected surface of a flange positioned on the upper side when lifted up, is more inclined downward over the entire surface from the inner circumferential edge to the outer circumferential edge of the flange as it goes to the outside circumference. COPYRIGHT: (C)2010,JPO&INPIT
    • 要解决的问题:为了提供一种液体排放效果优异的法兰联轴器,从液体内部提升时,显着减少了用于擦拭液体所需的废物数量,显着降低了飞溅的风险 操作者上的液体,并且不会劣化强度,并且还提供具有管道的结构。

      解决方案:法兰联轴器用于具有管道的结构管道部分,该管道用于液体并根据需要从液体内部提起,并从液体的内部几乎提升 一级状态。 位于上侧的凸缘的非连接表面的上表面当升起时从凸缘的内周边缘到外周边缘的整个表面向下倾斜, 圆周。 版权所有(C)2010,JPO&INPIT

    • 13. 发明专利
    • Method and device for mixing lubricant and base metal powder
    • 用于混合润滑剂和基础金属粉末的方法和装置
    • JP2010100869A
    • 2010-05-06
    • JP2008271137
    • 2008-10-21
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • YOSHIMUTA HIDEJI
    • B22F1/00
    • PROBLEM TO BE SOLVED: To provide a method and device for mixing a lubricant and base metal powder, by which a lubricant and base metal powder are uniformly mixed.
      SOLUTION: Disclosed are the mixing method and device including: a heating stage and a heating part performing heating by an external heat type heat source in such a manner that a lubricant 4 is vaporized in a nonoxidizing gas 6; a mixing stage and a mixing part mixing base metal powder 5 and the vaporized lubricant in a batch system; a cooling stage and a cooling part cooling the base metal powder and the vaporized lubricant; and a regenerating stage and a lubricant regenerating part making the surplus lubricant to reutilize.
      COPYRIGHT: (C)2010,JPO&INPIT
    • 要解决的问题:提供一种混合润滑剂和贱金属粉末的方法和装置,通过该方法和装置将润滑剂和贱金属粉末均匀混合。 解决方案:公开了混合方法和装置,其包括:加热阶段和通过外部热式热源进行加热的加热部分,使得润滑剂4在非氧化气体6中蒸发; 混合阶段和混合部分混合贱金属粉末5和蒸发的润滑剂在批量系统中; 冷却阶段和冷却基体金属粉末和汽化润滑剂的冷却部件; 以及使剩余润滑剂再利用的再生阶段和润滑剂再生部。 版权所有(C)2010,JPO&INPIT
    • 14. 发明专利
    • Device for measuring thickness of oxide film of fuel rod
    • 测量燃料氧化膜厚度的装置
    • JP2010091403A
    • 2010-04-22
    • JP2008261525
    • 2008-10-08
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • UEDA MASAHARUSEKI TATSUO
    • G21C17/06G21C3/02G21C3/06
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To take an efficient and accurate measurement of the thickness of oxide films of fuel rods, including such preparation work as the removal of clad on the surface of the fuel rods and calibration work.
      SOLUTION: The device includes a measurement probe 20 for measuring the thickness of oxide films on the surface of fuel rods of an underwater fuel assembly 1 mounted on a frame 12 and a clad removal jig 30 mounted also on the frame 12 to remove the clad on the surface of the fuel rods and is also equipped with a probe positioning guide 22 for breaking through lines 1L of the fuel rods to guide the measurement probe 20 toward the surface of a fuel rod 1R to be measured when the probe 20 is pressed on the surface of the fuel rod 1R to be measured. First of all, the clad removal jig 30 is put into touch with the fuel rod 1R to be measured to remove the clad. Then, the frame 12 is reoriented to put the measurement probe 20 into touch with the fuel rod 1R and measure the thickness of the oxide film.
      COPYRIGHT: (C)2010,JPO&INPIT
    • 要解决的问题:对燃料棒氧化膜的厚度进行有效和准确的测量,包括在燃料棒表面上去除包层的校准工作。 解决方案:该装置包括测量探针20,用于测量安装在框架12上的水下燃料组件1的燃料棒表面上的氧化物膜的厚度以及也安装在框架12上以除去 燃料棒表面上的包层并且还配备有探针定位引导件22,用于穿过燃料棒的线路1L,以便当探针20为探针20时将测量探针20朝向待测量的燃料棒1R的表面引导 压在要测量的燃料棒1R的表面上。 首先,将包覆除去夹具30与要测量的燃料棒1R接触以去除包层。 然后,将框架12重新定向以使测量探针20与燃料棒1R接触并测量氧化膜的厚度。 版权所有(C)2010,JPO&INPIT
    • 15. 发明专利
    • Method and apparatus for regulating uranium enrichment for high-temperature gas-cooled reactor
    • 用于调节高温气体冷却反应器的铀浓缩的方法和装置
    • JP2010006618A
    • 2010-01-14
    • JP2008164919
    • 2008-06-24
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • YASUDA ATSUSHITAKAHASHI MASASHI
    • C01G43/00
    • Y02E30/33Y02E30/38
    • PROBLEM TO BE SOLVED: To provide a method and an apparatus for regulating an uranium enrichment of a fuel for a high-temperature gas-cooled reactor, which does not need waste fluid treatment and can shorten treatment time. SOLUTION: At least two U 3 O 8 powder aggregates are selected from a plurality of U 3 O 8 powder aggregates having different uranium enrichments each other and each having 4.8 KgU or less in terms of uranium. Amounts proportionally distributed so that the total weighed amount becomes 4.8 KgU or less in terms of uranium and makes a desired uranium enrichment are weighed and collected respectively from the selected plurality of U 3 O 8 powder aggregates. After the difference between the total value X of weighed values of respective weighed U 3 O 8 powder aggregates and the weighed value Y of a united U 3 O 8 powder aggregate obtained by uniting respecrive weighed U 3 O 8 powder aggregates is checked to be within the range of a prescribed threshold value, uranyl nitrate is formed by dissolving the united U 3 O 8 powder aggregate in nitric acid. COPYRIGHT: (C)2010,JPO&INPIT
    • 要解决的问题:提供一种用于调节用于高温气冷反应堆的燃料的铀浓缩的方法和装置,其不需要废液处理并且可以缩短处理时间。

      解决方案:至少两个U SB 3 O SB SB 8粉末聚集体选自多个U SB 3 O 3 / SB>具有彼此不同的铀浓缩物并且各自具有4.8kgU或更小的铀的粉末聚集体。 按比例分配的量,使得总称重量以铀计为4.8KgU或更低,并且从所选择的多个U SB 3中分别称取和收集所需的铀浓缩物, SB>粉末聚集体。 在各个称重的U 3 SBB粉末聚集体的称重值的总值X与合并U SB 3的SB的加权值Y之差 将通过结合重量的重量为3g / kg的粉末聚集体获得的粉末聚集体检查在规定的阈值范围内, 硝酸铀酰是通过将联合的U 3 SBB粉末骨料溶解在硝酸中形成的。 版权所有(C)2010,JPO&INPIT

    • 16. 发明专利
    • Lower tie plate for fuel assembly and fuel assembly for boiling water reactor equipped with same
    • 用于燃料装配的下层板和燃料组件用于与其配套的锅炉水反应器
    • JP2009085594A
    • 2009-04-23
    • JP2007251531
    • 2007-09-27
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • OWAKI MICHIOSEKIGUCHI MAMORUSAKAI HITOSHI
    • G21C3/33
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To provide a lower tie plate where the work for profiling the corner parts of a prism section like the letter of R can be carried out in a shorter time at lower costs and more efficiently than ever and a fuel assembly for a boiling water reactor equipped with the lower tie plate.
      SOLUTION: In the lower tie plate for the fuel assembly, the outline contours of the cross sections running in the orthogonal direction to the vertical axis in the four corner parts on the outer peripheral surface of the prismatic section with insertion holes to support the lower part of fuel rods and water pipes and cooling water circulation holes on its upside have polygonally chamfered shapes inscribed in predetermined arcs respectively.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:为了提供一种下层连接板,其中可以在更短的时间内以更低的成本和比以往更高效的方式在诸如R的字母的棱镜部分的角部分进行成型的工作,并且燃料 装配有下连接板的沸水反应堆的组装。 解决方案:在用于燃料组件的下连接板中,在具有插入孔的棱柱形部分的外周表面上的四个角部分中与垂直轴正交的横截面的轮廓线轮廓被支撑 燃料棒的下部和水管及其上部的冷却水循环孔分别具有以预定弧形刻录的多边形倒角形状。 版权所有(C)2009,JPO&INPIT
    • 17. 发明专利
    • Cask storage frame
    • CASK储物架
    • JP2009014663A
    • 2009-01-22
    • JP2007179790
    • 2007-07-09
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • AOKI TOYOKAZUKITAGAWA YUJI
    • G21C19/32G21F5/14G21F9/36
    • PROBLEM TO BE SOLVED: To provide a cask storage frame which fixes a cask and is transported by an air pallet in cask storage facilities, and is suitable for cooling the bottom face of the cask.
      SOLUTION: The cask storage frame comprises: a top plate; a bottom plate; a plurality of webs installed between the top plate and the bottom plate and connecting them; and legs, and can be transported by an air pallet. An opening is provided in the top plate, and the webs are arranged to allow air to flow from the outer side face of the cask storage frame to the opening.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:提供一种用于固定一个桶并由一个空气托盘运输在一个储物库中的桶储存框架,并且适用于冷却该桶的底面。 解决方案:储物架包括:顶板; 底板; 安装在顶板和底板之间并连接它们的多个网; 和腿,并可以通过空气托盘运输。 在顶板中设有开口,并且腹板设置成允许空气从储物架的外侧面流向开口。 版权所有(C)2009,JPO&INPIT
    • 18. 发明专利
    • Method and device for setting equivalent coefficient and method and device for converting uranium isotope
    • 用于设置等效系数的方法和装置以及用于转换铀同位素的方法和装置
    • JP2009014511A
    • 2009-01-22
    • JP2007176600
    • 2007-07-04
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • HANAYAMA YASUSHI
    • G21C3/328G21C3/62G21C17/06
    • Y02E30/38
    • PROBLEM TO BE SOLVED: To set equivalent coefficients of U isotopes, Np fuel and burnable poison which are not listed in equivalent coefficient tables that have already been prepared.
      SOLUTION: As to MOX fuel which contains one or more kinds of U isotopes that are not listed in the already-prepared equivalent coefficient tables because an equivalent fissile method is used for MOX fuel and also belongs to the same group in an equivalent coefficient table; required set numbers of the composition of U in the MOX fuel are set, MOX fuel with a representative composition in the group to which the set MOX fuel belongs is found and a reference point determined by the enrichment, burnup and infinite multiplication factor of the found MOX fuel is established. As to each MOX fuel where the required set numbers of the composition of U are set, then, the enrichment satisfying the reference point is found in prescribed procedures by using computational codes used to establish the reference point. Subsequently, the equivalent coefficients of the U isotopes which are not listed in the equivalent coefficient tables are obtained on the basis of the enrichment found as to each MOX fuel where the required set numbers of the composition of U are set, an equivalent fissile method and the equivalent coefficient tables.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:设置在已经准备好的等效系数表中未列出的U同位素,Np燃料和可燃毒物的等效系数。

      解决方案:对于含有一种或多种U同位素的MOX燃料,由于使用等效的易裂变方法用于MOX燃料,也属于等效的等效系数表中的相同组 系数表; 设定MOX燃料中U的组成的所需设定数,找到具有组合MOX燃料所属的组中的代表性组成的MOX燃料,并且通过发现的浓缩,燃耗和无限倍增因子确定的参考点 MOX燃料成立。 对于设定了所需组合U的每个MOX燃料,则通过使用用于建立参考点的计算代码,在规定的程序中找到满足参考点的浓缩。 随后,在等效系数表中未列出的U同位素的等效系数基于对设定U的组成的所需设定数的每个MOX燃料的浓缩,等效的易裂变法和 等效系数表。 版权所有(C)2009,JPO&INPIT

    • 19. 发明专利
    • Method and apparatus for detoxifying organic halogen compound
    • 用于脱氧有机卤素化合物的方法和装置
    • JP2008271998A
    • 2008-11-13
    • JP2006280656
    • 2006-10-13
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • INAGAWA SATOSHIKIYAMA YOICHINAKAGOME NOBORU
    • A62D3/30A62D101/22B01J19/00C07B35/06C07C25/18
    • PROBLEM TO BE SOLVED: To stably and continuously detoxify even PCB in which the content of chlorine is variously different or PCB containing impurities or other components.
      SOLUTION: The method for detoxifying an organic halogen compound has a concentration adjustment step of adjusting the halogen concentration of the organic halogen compound to be fixed prior to detoxifying the organic halogen compound. The organic halogen compound is the PCB and a chlorine concentration is adjusted in the concentration adjustment step. In the concentration adjustment step, the organic halogen compound is diluted with insulating oil to fix the halogen concentration. In the concentration adjustment step, the halogen concentration is turned to a fixed value within 20±10 wt.%.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:为了使氯的含量各不相同的PCB或含有杂质或其他组分的PCB的均匀连续地解毒。 解决方案:有机卤素化合物的解毒方法具有将有机卤素化合物的卤素浓度调节为在有机卤素化合物解毒之前固定的浓度调节步骤。 有机卤素化合物是PCB,并且在浓度调节步骤中调节氯浓度。 在浓度调节步骤中,用绝缘油稀释有机卤素化合物以固定卤素浓度。 在浓度调节步骤中,卤素浓度变为固定值在20±10重量%以内。 版权所有(C)2009,JPO&INPIT
    • 20. 发明专利
    • Nuclear facility wind removal device
    • 核设备风力除去装置
    • JP2008058047A
    • 2008-03-13
    • JP2006232958
    • 2006-08-30
    • Nuclear Fuel Ind Ltd原子燃料工業株式会社
    • YOSHIMUTA HIDEJI
    • G21F7/005E06B7/084G21F3/00
    • PROBLEM TO BE SOLVED: To provide a nuclear facility wind removal device having a simple and inexpensive configuration, capable of showing steadily radiation shielding function in a nuclear facility, facilitating atmosphere management and atmosphere stabilization, and improving working efficiency when carrying in continuously or carrying out continuously a nuclear material.
      SOLUTION: A cylindrical carrying-in/out chamber 21 is provided in the nuclear facility 11 for carrying in/out the nuclear material X. The carrying-in/out chamber 21 has an outside opening 22 formed on a carrying-in/out chamber wall facing to the outside of the nuclear facility 11 and an inside opening 23 formed on a carrying-in/out chamber wall facing to the inside of the nuclear facility 11. A rotator 31 having a plurality of radially-distributed rotating walls 33 is installed rotatably in the carrying-in/out chamber 21. The interval between the outside opening 22 and the inside opening 23 in the carrying-in/out chamber 21 is shielded steadily by the plurality of rotating walls 33 regardless of a rotational displacement of the rotator 31 in a relative relation between the carrying-in/out chamber 21 and the rotator 31.
      COPYRIGHT: (C)2008,JPO&INPIT
    • 要解决的问题:提供一种具有简单廉价的构造的核设施除风装置,能够在核设施中显示出稳定的辐射屏蔽功能,便于气氛管理和大气稳定,并且在连续进行时提高工作效率 或连续进行核材料。 解决方案:在核设施11中设置有用于携带/取出核材料X的圆柱形进/出室21.进入/离开室21具有形成在进入的外部开口22 /出室壁朝向核设施11的外部,以及形成在面向核设施11的内部的进/出室壁上的内部开口23.具有多个径向分布的旋转壁的旋转体31 33可旋转地安装在输入/输出室21中。不管旋转位移如何,通过多个旋转壁33稳定地屏蔽进出室21中的外部开口22和内部开口23之间的间隔 (C)2008,JPO&INPIT(2008),JPO&INPIT